ML20009H205
| ML20009H205 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/24/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20009H203 | List: |
| References | |
| IEB-80-06, IEB-80-6, NUDOCS 8108070024 | |
| Download: ML20009H205 (2) | |
Text
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SAFETY EVALUATION REPORT MILLSTONE NUCLEAR POWER STATION, UNIT 1 LICENSEE RESPONSE TO I&E BULLETIN 80-06, j
ENGINEERED SAFETY FEATURES (ESP) RESET CONTROLS INTRODUCTION Instances have been reported at operating nuclear power plants where it had been found that following the reset of an ESF actuated signal, certain equipment (e.g., ventilation dampers, motors, and valves) would return to its normal mode which could compromise the protective-actions of the affected systems.
As a result, on March 13, 1980 the NRC issued I&E Bulletin 80-06 requesting certain actions to be taken by licensees for all PWR r.nd BWR facilities with operating licenses.
EVALUATION
-The enclosed report (EGG 1183-4219) was prepared for us by E G & G, Inc.,
San Ramon, California as part of our technical assistance contractor program.
It provides their technical evaluation of the licensee's response to IaE Bulletin 80-06 in accordance with NRC-provided guidance.
For all safety systems, E G & G concluded that safety-related equipment remains in its emergency mode upon reset of the ESF actuated signals, except for the four identified ESF devices (iso-condenser valves) found to change position upon ESFAS reset. The licensee provided a detailed modification scheme for these devices which E G & G concluded will ausure that the identified de-vices will remain in their emergency mode position upon ESFAS reset.
- Further, the licensee committed to modify and test these systems during the February 1981 refueling outage, to demonstrate compliance. Therefore, E G & G found the plant to satisfy the requirements of I&E Bulletin 80-06.
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. CONCLUSION I
Based on the infomation and documents provided by the licensee, and on our review of the contractor's report, we conclude that the licensee has satisfied the concerns of I&E Bulletin 80-06, subject to the successful completion of confirmatory testing. Therefore, we find the ESF reset controls for the Millstone Nuclear Power Station Unit 1 in compliance with NRC criteria.
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